The T-containment properties of a Zr-containing Li rod in a high-temperature gas-cooled reactor as a T production device for fusion reactors
The T-containment properties of a Zr-containing Li rod in a high-temperature gas-cooled reactor as a T production device for fusion reactors
复制标题
高温气冷堆中含锆锂棒作为聚变反应堆产T装置的T容纳特性
DOI：
10.1016/j.fusengdes.2021.112441
复制
发表时间：
2021
影响因子：
1.7
通讯作者：
Y. Sakamoto
中科院分区：
文献类型：
--
作者：
H. Matsuura;Takuro Suganuma;Yukina Koga;Motomasa Naoi;K. Katayama;T. Otsuka;M. Goto;S. Nakagawa;Shinpei Hamamoto;E. Ishitsuka;K. Tobita;S. Konishi;R. Hiwatari;Y. Someya;Y. Sakamoto
利用高温气冷堆（HTGRs）生产氚（T）是为了在示范聚变堆中进行T处理和初始T拥有的工程研究。在高温气冷堆运行过程中，锂棒中T的稳定包容是一个关键问题。本研究调查了这一辐照试验，以检查T-遏制性能在锂加载棒，并开发了一个分析模型，评估T流出量的He冷却剂。假设HTGR设置，实验测量氢吸收特性，包括在Zr充分吸收氢之后氢吸收速度的劣化。我们提出了一个分析模型，评估从锂棒的T流出，并在此模型的基础上，估计总T流出，假设存在的燃气轮机高温反应堆的300兆瓦的标称容量和高温工程试验堆。它表明，通过加载到锂棒中的Zr的足够量，T流出可以被抑制到小于一个小的百分比的总T在360天的反应堆运行期间产生的。
The production of tritium (T) using high-temperature gas-cooled reactors (HTGRs) has been studied for a prior engineering research with T handling and initial T possession in demonstration fusion reactors. Stable containment of T in Li-loading rods during HTGR operation is a critical issue. This study investigates this for an irradiation test to examine T-containment performance in Li-loading rods and develops an analytical model of evaluating the amount of T outflow to a He coolant. The hydrogen absorption characteristics, including the deterioration of the hydrogen absorption speed after Zr has sufficiently absorbed the hydrogen, is experimentally measured assuming an HTGR setting. We present an analytical model of evaluating the T outflow from a Li rod and, on the basis of this model, estimate the total T outflow, assuming the presence of a gas-turbine high-temperature reactor of 300 MWe with a nominal capacity and a high-temperature engineering test reactor. It is demonstrated that, by loading a sufficient amount of Zr into the Li rod, the T outflow can be suppressed to less than a small percent of the total T produced during 360 days of reactor operation.
高温气冷堆演示聚变堆制氚的方法
DOI：
--
发表时间：
2014
期刊：
Plasma Conf 2014 CD-ROM
影响因子：
--
作者：
Hiroyuki Nakaya;Hideaki Matsuura;Kazunari Katayama;Minoru Goto;Shigeaki Nakagawa;Keniji Tobita;Yuji Someya;Makoto Nakamura
通讯作者：
Makoto Nakamura
聚变反应堆高温气冷堆用锆和氧化铝约束氚制氚的研究
DOI：
--
发表时间：
2021
期刊：
影响因子：
--
作者：
Hiroki Isogawa;Kazunari Katayama;Hideaki Matsuura
通讯作者：
Hideaki Matsuura
聚变反应堆高温气冷堆中产氚的氧化铝和锆的氚限制性能评价
DOI：
--
发表时间：
2014
期刊：
影响因子：
--
作者：
Kazunari Katayama;Hiroki Ushida;Hideaki Matsuura;Satoshi Fukada;Minoru Goto;Shigeaki Nakagawa
通讯作者：
Shigeaki Nakagawa